中国高温气冷堆核电示范工程环境辐射影响初步分析  

Preliminary Radiological Consequence Assessment of China Pilot HTR Power Plant

作　　者：曲静原[1] 曹建主[1] 李红[1] 刘原中[1] 方栋[1] 

机构地区：[1]清华大学核能与新能源技术研究院,北京100084

出　　处：《核动力工程》2006年第6期109-112,共4页Nuclear Power Engineering

摘　　要：对我国高温气冷堆核电示范工程(HTR-PM)进行了环境辐射影响分析和评价。内容包括堆芯放射性总量的计算、正常运行工况下放射性核素的年释放量、事故源项的分析计算以及正常运行和事故情况下辐射剂量的估计。分析结果表明:正常运行工况下,HTR-PM放射性释放对公众成员可能产生的辐射剂量远低于我国目前的法规要求;设计基准事故情况下对公众成员可能产生的辐射剂量明显低于需要在场外采取隐蔽措施的通用干预水平。This paper presents the major results of a preliminary assessment on the radiological impact of China pilot HTR power plant. They include the calculation of inventory of radio-nuclides in the reactor core, release of radioactivity into the atmosphere during routine operation, source term of release and the resuiting radiation dose in the event of an accident. The results of this assessment have shown that the radiation dose received by the general public as a result of radioactivity release under normal operation conditions will be far below the dose limit defined in national regulations. The potential exposure to the population in the event of design basis accidents will be significantly lower than the generic intervention levels for taking sheltering.

关 键 词：模块式高温气冷堆 示范电站 源项 事故后果评价 

分 类 号：TL424[核科学技术—核技术及应用]